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The paper describes the public participation from the viewpoint of a stakeholder and member of the public. The dialogue between various members of the Dounreay Stakeholders Committee vary widely and do not always seem to represent the views of the wider public. Whilst great care has been taken to select various options for the ultimate condition of the Dounreay site and these have been discussed at great length and the preferred option selected by consensus, there still appears to be some conflict within the local community. It is probable that if the local population had to vote on the options for the future of the Dounreay nuclear site the outcome would be vastly different from that of the Stakeholders Committee. Whilst the politicians have been elected by the people, they represent a distinctly anti-nuclear view (even to the extent of decommissioning) whereas many local people (especially the workers on the Dounreay site) would prefer to see a continuation of nuclear activity at Dounreay. The problem is not only with local politicians but at national level in Scotland itself where the Scottish National Party has formed a coalition with the Green Party on condition all nuclear activities are phased out.Copyright © 2009 by ASME

Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m2 , concrete volume 12,500 m3 , and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building has been divided into three parts — each part is isolated from the others. In September 2008 the eastern part of the building has been demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS strategy will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also specific breathing and cooling air systems have been provided to allow the operators to carry out the decommissioning tasks in acceptable working conditions.Copyright © 2009 by ASME

The need exists in the nuclear world to reduce the doses to the workers in radioactive environments be it in routine maintenance or in decommissioning activities. A key factor in satisfying this need is the availability of a fast and adequate characterization and modeling of the work area. In this paper we propose a method to combine gamma and geometrical scanning measurements with the modeling and source fitting capabilities of the VISIPLAN 3D ALARA planning tool to model a nuclear site. The presentation also includes the application of human modeling tools to assess the dose to the worker for a given task. The characterization method is demonstrated based on an application in an industrial site.

The decommissioning of Windscale Pile 2 Chimney resulted in the removal of one of most historically significant and prominent features of the Sellafield site. The project was the first large scale concrete “free release” operation to be undertaken on the Sellafield nuclear site, producing 4500 tons of concrete of which 3000 tons was demonstrated to be “free release”. The paper describes the radiometric techniques employed in the characterization and segregation of the concrete into Low Level Waste (LLW), Very Low Level Waste (VLLW) and Free Release categories. It examines the robust solutions that were developed to meet the technical and regulatory challenges of the project, which included the definition of free release, the selection of averaging volumes, the testing and validation of the monitoring systems employed for bulk quantities of concrete and the identification and removal of small numbers of fuel particles from the free release waste stream. As a result of interest shown by other BNFL and UKAEA decommissioning projects at Sellafield, the paper finishes by discussing ways in which the system may be developed to assay other waste streams.Copyright © 2003 by ASME

In 1997 Nirex failed to obtain planning permission to build an underground laboratory (Rock Characterisation Facility) near the Sellafield nuclear site in Cumbria, North-West England. This stopped the UK’s deep disposal programme. Since then there has been much discussion on how the UK should take the issue of long-term radioactive waste management forward. As part of its contribution to the ongoing debate, Nirex needed to reassess how its role in finding a long-term solution could be better played given its history. It has been suggested that the processes required to deal with such a contentious issue, the conduct of individuals and the structural relationships between organisations, all need to change if any progress is to be made. Specifically, one of the difficulties of the past was the lack of a mechanism to allow all stakeholders and the public to clearly see what had been decided and for what reasons. It is suggested that central to these changes needs to be a strong ethical framework based on transparency. This paper will provide an overview of the Nirex Transparency Policy, its operation and some observations of putting it into practice. As a method of ensuring that Nirex does not get complacent about this important aspect of their work, it established an Independent Transparency Review Panel. As part of this panel’s remit they conduct an annual review of the operation of Nirex’s Transparency Policy. Some conclusions and recommendations of operating such a policy will be discussed as will the implications of forthcoming legislation.Copyright © 2003 by ASME